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Numerical Dosimetry: Applications in Radiation Protection


'The primary aim of radiological protection is to provide an appropriate standard of protection for man without unduly limiting the beneficial practices giving rise to radiation exposure'. This general objective, the as low as reasonably achievable (ALARA) principle, may be considered as the philosophy governing the assessment of risk encountered by persons exposed to ionising radiations. For instance, radiation hazards exist in the nuclear power industry, in the (re)processing of radioactive fuel, in medical, industrial and research applications of isotopes, and around accelerators. Radiation protection dosimetry provides a quantitative basis for verifying that exposure conditions of individuals are well below recommended dose limits, expressed in terms of protection quantities defined in ref. To achieve this task, radiation protection dosimetry relies on indications (or readings) of dosimetric devices, calibrated in terms of ICRU operational quantities, considered as appropriate to perform satisfactory ambient and individual monitoring at workplaces. It is generally agreed that radiation protection dosimetry at a monitored area involves mainly a combination of radiation physics and measurements with survey instruments and/or personal dosimeters. But, for the last decade, the support of numerical [or the recommended 'computational' (4)] dosimetry has continuously increased. Several reasons can be proposed: 1) The concepts of protection and operational quantities which, as weighted-absorbed dose quantities, do not lend themselves to an easy, or even achievable, experimental approach; 2) the distribution of general Monte Carlo codes, able to deal with radiation transport in very complicated geometries, and evaluated cross section data libraries; 3) the availability of cheaper high-speed PCs or workstations; and 4) economic constraints favouring the substitution of generally expensive experiments by simulation calculations. As a result, it is now current practice to accompany an experiment in the field of dosimetry for radiation protection purposes by a computational simulation. In this paper, only a few examples of such recent 'combined' realisations are mentioned, this selection being restricted to situations of external exposure to photons, neutrons and β particles.......

【作者名称】: J-L. Chartier
【作者单位】: Institut de Protection et de Surete Nucleaire-CEA, B.P. 6, 92265 Fontenay-aux-Roses, Cedex, France
【关 键 词】: Numerical Dosimetry: Applications in Radiation Protection
【会议名称】: 11th International Congress of Radiation Research Jul 18-23, 1999 Dublin, Ireland
【期刊论文数据库】: [DBS_Articles_01]
【期刊论文编号】: 100,835,259
【摘要长度】: 2,307
【会议地点】: Dublin(IE);Dublin(IE)
【会议组织】: Institut de Protection et de Surete Nucleaire-CEA, B.P. 6, 92265 Fontenay-aux-Roses, Cedex, France
【会议时间】: 1999
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